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JPS5840719B2 - Cleaning equipment for nuclear fuel bodies in use at nuclear reactor facilities - Google Patents
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JPS5840719B2 - Cleaning equipment for nuclear fuel bodies in use at nuclear reactor facilities - Google Patents

Cleaning equipment for nuclear fuel bodies in use at nuclear reactor facilities

Info

Publication number
JPS5840719B2
JPS5840719B2 JP51039207A JP3920776A JPS5840719B2 JP S5840719 B2 JPS5840719 B2 JP S5840719B2 JP 51039207 A JP51039207 A JP 51039207A JP 3920776 A JP3920776 A JP 3920776A JP S5840719 B2 JPS5840719 B2 JP S5840719B2
Authority
JP
Japan
Prior art keywords
cleaning
nuclear fuel
nuclear
tank
fuel assembly
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired
Application number
JP51039207A
Other languages
Japanese (ja)
Other versions
JPS52122793A (en
Inventor
政夫 喜多村
俊介 内田
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Hitachi Ltd
Original Assignee
Hitachi Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP51039207A priority Critical patent/JPS5840719B2/en
Publication of JPS52122793A publication Critical patent/JPS52122793A/en
Publication of JPS5840719B2 publication Critical patent/JPS5840719B2/en
Expired legal-status Critical Current

Links

Classifications

    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Cleaning By Liquid Or Steam (AREA)
  • Cleaning In General (AREA)

Description

【発明の詳細な説明】 本発明は原子炉に於て使用中の核燃料体を洗浄するため
の洗浄装置に関し、特に沸騰水形軽水原子炉に好適する
使用中の核燃料体の洗浄装置に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a cleaning device for cleaning nuclear fuel assemblies in use in a nuclear reactor, and particularly to a cleaning device for nuclear fuel assemblies in use that is suitable for a boiling water light water reactor.

沸騰水形原子炉の炉心を構成する核燃料体の外周面には
、冷却材である軽水に運ばれた不純物が付着することが
知られている。
It is known that impurities carried by light water, which is a coolant, adhere to the outer circumferential surface of a nuclear fuel assembly that constitutes the core of a boiling water reactor.

核燃料体外周面における大量の不純物の付着は核燃料体
の伝熱効率を低下させ、この結果、核燃料体の被覆管の
腐蝕による破損を引き起す。
Adhesion of a large amount of impurities on the outer circumferential surface of the nuclear fuel assembly reduces the heat transfer efficiency of the nuclear fuel assembly, resulting in damage to the cladding tube of the nuclear fuel assembly due to corrosion.

また、被覆管の破損に至らない量の不純物の付着の場合
も、これらの付着不純物が原子炉運転中に放射能を帯び
、これが剥離して冷却材とともに一次系配管に送られて
配管表面に付着し、この結果、−次系配管の表面におけ
る放射線量が増加する。
In addition, even in the case of adhesion of impurities in amounts that do not cause damage to the cladding, these adhering impurities become radioactive during reactor operation, peel off and are sent to the primary system piping along with the coolant, and are deposited on the piping surface. As a result, the radiation dose on the surface of the secondary system piping increases.

、このため、核燃料体の外周面に付着した不純物を除去
する必要があり、原子炉の運転停止時に燃料体を洗浄す
ることが必要となる。
Therefore, it is necessary to remove impurities adhering to the outer peripheral surface of the nuclear fuel assembly, and it is necessary to clean the fuel assembly when the reactor is shut down.

燃料体の洗浄方法として原理的には化学的洗浄法と物理
的洗浄法とが考えられるが、化学的洗浄法には下記のよ
うな問題点があり、核燃料体の洗浄法としては採用でき
ない。
In principle, chemical cleaning methods and physical cleaning methods can be considered as methods for cleaning fuel bodies, but chemical cleaning methods have the following problems and cannot be adopted as a method for cleaning nuclear fuel bodies.

すなわち、核燃料体の洗浄法として化学的洗浄法を採用
した場合、使用後に化学薬品が核燃料体外周面に付着し
たり、或いは炉水中への拡散によつて炉水中に数ppd
程度の濃度で残留することは避けられない。
In other words, when a chemical cleaning method is adopted as a nuclear fuel assembly cleaning method, chemicals may adhere to the outer surface of the nuclear fuel assembly after use, or several ppd may be present in the reactor water due to diffusion into the reactor water.
It is unavoidable that some concentrations remain.

この残留化学薬品が原子炉運転再開時に活性化して炉心
及びその他の部分に腐蝕や、応力腐蝕割れ及びその他の
悪影響を及ぼすことが予想され、極めて危険である。
This residual chemical is expected to become activated when the reactor restarts, causing corrosion, stress corrosion cracking, and other adverse effects on the reactor core and other parts, which is extremely dangerous.

一方、物理洗浄法を採用する場合には、従来、火力発電
プラントの復水器配管洗浄に使用実績のあるスポンジポ
ール洗浄法が有効と考えられるが、この洗浄法を採用し
た場合、復水器配管内径に比べて核燃料棒間の流路は極
めて狭い上、スペーサ等の微細は構造物も含まれている
ので、スポンジポールが詰って流路を閉塞する恐れがあ
る。
On the other hand, when adopting a physical cleaning method, the sponge pole cleaning method, which has been used in the past for cleaning condenser piping in thermal power plants, is considered to be effective; The flow path between the nuclear fuel rods is extremely narrow compared to the inner diameter of the piping, and it also contains minute structures such as spacers, so there is a risk that the sponge poles will become clogged and block the flow path.

しかしながら、物理洗浄法によれば、化学洗浄法のよう
に洗浄後に機器に悪影響を及ぼす心配は少いと考えられ
るので、化学洗浄法よりは核燃料体の洗浄法として有効
であると考えられる。
However, the physical cleaning method is considered to be more effective as a method for cleaning nuclear fuel bodies than the chemical cleaning method because it is thought that there is less concern about adverse effects on the equipment after cleaning as in the case of the chemical cleaning method.

そこで、固体粒子による核燃料体内流路の閉塞を避ける
ために固体粒子として一定温度以上で融解しうる氷もし
くは低融点パラフィン等の易融解性固体粒子を使用し、
固体粒子の配管内への詰りを防止することにより、物理
洗浄法を欠点除去のうえ有効に利用することが従来種々
考えられている0 ところが従来では、洗浄部において放射線の遮蔽効果を
十分に行なうのに複雑な構成、装備を必要としている。
Therefore, in order to avoid blockage of the flow path in the nuclear fuel by solid particles, easily meltable solid particles such as ice or low melting point paraffin, which can be melted at a certain temperature or higher, are used as solid particles.
It has been considered in the past that physical cleaning methods can be used effectively to eliminate defects by preventing solid particles from clogging pipes. However, it requires a complex configuration and equipment.

また、固形物質の後処理も十分でなく、洗浄効果が不十
分となることがある。
Furthermore, the post-treatment of solid substances may not be sufficient, resulting in insufficient cleaning effects.

本発明の目的は、洗浄部における放射線の遮蔽効果が確
実であり、かつ洗浄能率も高い原子炉施設における使用
中の核燃料体の洗浄装置を提供することを目的とする。
SUMMARY OF THE INVENTION An object of the present invention is to provide a cleaning device for a nuclear fuel assembly in use in a nuclear reactor facility, which has a reliable radiation shielding effect in a cleaning section and has high cleaning efficiency.

本発明の特徴は原子炉圧力容器が浸漬される燃料交換用
プール及び使用前の核燃料を貯蔵する貯蔵プール等を有
した原子炉施設において使用中の核燃料体を洗浄する洗
浄装置にして、前記燃料交換用プールもしくは貯蔵プー
ルのプール水中に水没されるとともに前記プール水から
隔絶された洗浄槽と、前記洗浄槽に接続され前記洗浄槽
内に洗浄液を貫通せしめる洗浄液供給装置とを含み、前
記洗浄液供給装置は、ポンプと、温度融解性固形物質の
供給装置と、汚物分離器と、を有することにある。
The present invention is characterized in that it is a cleaning device for cleaning a nuclear fuel assembly in use in a nuclear reactor facility having a fuel exchange pool in which a reactor pressure vessel is immersed, a storage pool for storing nuclear fuel before use, etc. A cleaning tank submerged in pool water of a replacement pool or a storage pool and isolated from the pool water, and a cleaning liquid supply device connected to the cleaning tank and allowing cleaning liquid to penetrate into the cleaning tank, the cleaning liquid supply device The device comprises a pump, a supply device for temperature-melting solid substances, and a waste separator.

以下に添附図面を参照して本発明の実施例について説明
する。
Embodiments of the present invention will be described below with reference to the accompanying drawings.

まず、第1図及び第2図を参照して本発明の第一実施例
について説明する。
First, a first embodiment of the present invention will be described with reference to FIGS. 1 and 2.

第1図は本発明の洗浄方法を実施するための装置の構成
を示すものであり、本発明を沸騰軽水形原子炉施設に適
用した例を示す。
FIG. 1 shows the configuration of an apparatus for carrying out the cleaning method of the present invention, and shows an example in which the present invention is applied to a boiling light water reactor facility.

第1図に於て、1は原子炉圧力容器であり、原子炉圧力
容器1は原子炉格納施設内の燃料交換用プール2のプー
ル水中に水没状態で浸漬されている。
In FIG. 1, 1 is a reactor pressure vessel, and the reactor pressure vessel 1 is submerged in water of a fuel exchange pool 2 in a reactor containment facility.

原子炉圧力容器1の中には、核燃料体を多数集束して構
成される炉心3と、炉心3を包囲して配置されたシュラ
ウド4と、シュラウド4のまわりに配置され上部プレナ
ムと下部プレナブとを連通ずる数個のジェットポンプ5
と、が収容されている。
Inside the reactor pressure vessel 1 are a reactor core 3 composed of a large number of nuclear fuel assemblies, a shroud 4 disposed surrounding the reactor core 3, and an upper plenum and a lower plenub disposed around the shroud 4. several jet pumps that communicate
and are accommodated.

第1図に於ては核燃料体の洗浄のために原子炉圧力容器
1の蓋が除かれた状態が示されており、従って圧力容器
1内の炉水と燃料交換用プール2のプール水とが混合さ
れている。
Figure 1 shows the state in which the lid of the reactor pressure vessel 1 has been removed for cleaning the nuclear fuel assembly, so that the reactor water in the pressure vessel 1 and the pool water in the fuel exchange pool 2 are separated. are mixed.

燃料交換用プール2のプール水中には、該プール水と隔
絶された洗浄槽6が水没状態に浸漬されている。
A cleaning tank 6 isolated from the pool water is submerged in the pool water of the fuel exchange pool 2.

この洗浄槽6はたとえば筒状の密閉容器であ0、管路p
1.p2を介して地上の洗浄液供給装置7に接続されて
いる。
This cleaning tank 6 is, for example, a cylindrical airtight container 0, and the pipe line p
1. It is connected to the cleaning liquid supply device 7 on the ground via p2.

第2図は核燃料体30が収容されている洗浄槽6の詳細
構造を示すものである。
FIG. 2 shows the detailed structure of the cleaning tank 6 in which the nuclear fuel assembly 30 is accommodated.

第2図にみられるように、洗浄槽6は蓋61と本体62
とから戊る。
As shown in FIG. 2, the cleaning tank 6 has a lid 61 and a main body 62.
Tokara.

蓋61と本体62とはそれぞれ二重壁構造であり、それ
ぞれの外周壁61A、62Aとそれぞれの内周壁61B
、62Bとの間の空間Sは真空に保たれている。
The lid 61 and the main body 62 each have a double wall structure, with respective outer peripheral walls 61A and 62A and respective inner peripheral walls 61B.
, 62B is kept in a vacuum.

蓋61と本体62とのそれぞれの内周壁には断熱材61
C,62Cが被覆され、これにより槽6の断熱効果が一
層高められている。
A heat insulating material 61 is provided on each inner peripheral wall of the lid 61 and the main body 62.
C, 62C is coated, thereby further enhancing the heat insulating effect of the tank 6.

蓋61と本体62とのそれぞれの端部には管路P1.P
2に接続される接続管61D、62Dが取付けられ、こ
れらの接続管61D、62Dは洗浄槽6の内部空間に開
口している。
At each end of the lid 61 and the main body 62, there is a conduit P1. P
Connecting pipes 61D and 62D connected to the cleaning tank 6 are attached, and these connecting pipes 61D and 62D open into the internal space of the cleaning tank 6.

本体62の下部内周面には上方に向って円錐状に開く中
心孔を有するリング状フランジ62Eが取付けられ、こ
のフランジ62Eは第2図に示されるように核燃料体3
0が本体62内に挿入された時には核燃料体30の下部
クイプレート30Dの外周面と係合する受座となってい
る。
A ring-shaped flange 62E having a center hole that opens conically upward is attached to the lower inner circumferential surface of the main body 62, and this flange 62E is attached to the nuclear fuel assembly 3 as shown in FIG.
0 serves as a seat that engages with the outer peripheral surface of the lower clamp plate 30D of the nuclear fuel assembly 30 when inserted into the main body 62.

本体62の上端部内周面にはもう一個のフランジ62F
が取付けられ、このフランジ62Fの内周傾斜面aは核
燃料体30の本体62内への挿入に際してガイドとして
役立つO 核燃料体30(これは本発明には含まれないものである
が、簡単に説明する。
Another flange 62F is provided on the inner peripheral surface of the upper end of the main body 62.
is attached, and the inner peripheral inclined surface a of this flange 62F serves as a guide when inserting the nuclear fuel assembly 30 into the main body 62. do.

)はよく知られているように、平行に配列された多数の
燃料棒30Aと、燃料棒30Aを包囲して配置されたチ
ャンネルボックス30Bと、チャンネルボックス30B
の上下両端及び燃料棒30Aの両端を固定した上部クイ
プレート30C及び下部クイプレート30Dと、から戊
っている。
), as is well known, includes a large number of fuel rods 30A arranged in parallel, a channel box 30B surrounding the fuel rods 30A, and a channel box 30B.
The upper and lower ends of the fuel rod 30C and the lower end of the fuel rod 30A are fixed to each other.

一方、洗浄槽6の蓋61の内周面には第2図に示される
ように平板状のリング形フランジ61Eが固定され、こ
のフランジ61Eの下方には該フランジ61Eからはね
61Fを介して可動フランジ61Gが吊下されている。
On the other hand, a flat ring-shaped flange 61E is fixed to the inner circumferential surface of the lid 61 of the cleaning tank 6, as shown in FIG. A movable flange 61G is suspended.

この可動フランジ61Gはその外周縁に於て下方外側へ
向って広がる傾斜部分を有し、該フランジ61Gの下面
にはゴム等の柔軟材61Hが取付けられている。
The movable flange 61G has an inclined portion extending downward and outward at its outer peripheral edge, and a flexible material 61H such as rubber is attached to the lower surface of the flange 61G.

この柔軟材61Hは、洗浄さるべき核燃料体30が洗浄
槽本体62中に密封された時に核燃料体30のチャンネ
ルボックス30Bの上端に係合して核燃料体30を洗浄
槽6の中で確実に保持するためのものである。
This flexible material 61H engages with the upper end of the channel box 30B of the nuclear fuel assembly 30 when the nuclear fuel assembly 30 to be cleaned is sealed in the cleaning tank body 62, and securely holds the nuclear fuel assembly 30 in the cleaning tank 6. It is for the purpose of

憲61及び本体62のそれぞれの合せ面に於て外周面に
張り出している外周フランジ61J。
An outer periphery flange 61J protrudes from the outer periphery of the respective mating surfaces of the frame 61 and the main body 62.

62Gが形威され、この両フランジ61G、62Gを介
して蓋61と本体62とが一体化されるようになってい
る。
62G, and the lid 61 and main body 62 are integrated through these flanges 61G and 62G.

本体62に形成されている外周フランジ62Gの上面に
は蓋61の外周フランジ61Jを案内するための円錐面
すが形成されている。
A conical surface for guiding the outer circumferential flange 61J of the lid 61 is formed on the upper surface of the outer circumferential flange 62G formed on the main body 62.

本体62の外周フランジ62Gにはまた、板はね等の弾
性材から成る掛金すなわちラッチ62Hが取付けられて
おり、このラッチ62Hの先端は蓋61の外周フランジ
61Jの上面に強く係合されるものである。
A latch or latch 62H made of an elastic material such as a plate is also attached to the outer peripheral flange 62G of the main body 62, and the tip of this latch 62H is strongly engaged with the upper surface of the outer peripheral flange 61J of the lid 61. It is.

なお、第2図に於て符号Rで示されるのばOリングであ
り、フランジ62Eの内周面に設けられた0リングRは
洗浄時に洗浄液が核燃料体30のチャンネルボックス3
0Bの外周に沿って流れることを防止するためのもので
ある。
Note that the symbol R in FIG. 2 is an O-ring, and the O-ring R provided on the inner peripheral surface of the flange 62E is used to prevent cleaning liquid from flowing into the channel box 3 of the nuclear fuel assembly 30 during cleaning.
This is to prevent the water from flowing along the outer periphery of 0B.

次に、再び第1図を参照して本発明装置の一部に含まれ
る洗浄液供給装置7の構成について説明する。
Next, referring again to FIG. 1, the configuration of the cleaning liquid supply device 7 included in a part of the apparatus of the present invention will be explained.

洗浄液供給装置7は原子炉格納施設内の地上に設置され
、該装置7には洗浄液タンク71、汚物分離器72、ポ
ンプ73、融解性固形物質供給装置74、形状選別器7
5、混合器76、とを含み、これらの構成機器を接続す
る管路P1〜P3には弁■1.■2.■3.■4が設け
られている。
The cleaning liquid supply device 7 is installed on the ground in the reactor containment facility, and the device 7 includes a cleaning liquid tank 71, a filth separator 72, a pump 73, a soluble solid material supply device 74, and a shape sorter 7.
5 and a mixer 76, and the pipes P1 to P3 connecting these components are equipped with valves 1. ■2. ■3. ■4 is provided.

洗浄液タンク71に貯留された洗浄液は原子炉が軽水炉
の場合には水でよい。
The cleaning liquid stored in the cleaning liquid tank 71 may be water if the nuclear reactor is a light water reactor.

洗浄液タンク71の下流側に設置された汚物分離器72
は配管P2を通って洗浄槽6から戻ってきた洗浄液中の
汚物を除去するもので、種々の形式のフィルターを用い
ることができる。
A waste separator 72 installed downstream of the cleaning liquid tank 71
is for removing dirt from the cleaning liquid returned from the cleaning tank 6 through the pipe P2, and various types of filters can be used.

洗浄液中に混入される融解性固形物質は前記したように
氷やパラフィンなどであるが、氷を用いる場合には洗浄
液の温度を低く保つために洗浄族タンク71中に冷媒コ
イル77を設置すればよい。
As mentioned above, the meltable solid substance mixed into the cleaning liquid is ice, paraffin, etc. When ice is used, a refrigerant coil 77 is installed in the cleaning tank 71 to keep the temperature of the cleaning liquid low. good.

形状選別器75は一定寸法以上の融解性固形物質を除去
するもので、篩(ふるい)等を使用してもよい。
The shape sorter 75 removes meltable solid substances of a certain size or more, and a sieve or the like may be used.

次に第1図及び第2図を参照して本発明装置の使用につ
いて説明する。
Next, the use of the apparatus of the present invention will be explained with reference to FIGS. 1 and 2.

核燃料体洗浄のため原子炉の運転が停止され、炉心温度
が低くなった数日後に原子炉圧力容器1の蓋(図示せず
)が開放され、圧力容器1中の炉水は燃料交換プール2
中に放出され、燃料交換プール2は炉水で満される。
The reactor operation was stopped for cleaning the nuclear fuel body, and several days after the core temperature became low, the lid (not shown) of the reactor pressure vessel 1 was opened, and the reactor water in the pressure vessel 1 was transferred to the fuel exchange pool 2.
The refueling pool 2 is filled with reactor water.

炉心3から1個の核燃料体30が既設のクレーン(図示
せず)等を用いてプール2中に引き出され、同時に洗浄
槽6の蓋61があけられて核燃料体30は洗浄槽6の本
体62中へ吊り下される。
One nuclear fuel assembly 30 is pulled out from the reactor core 3 into the pool 2 using an existing crane (not shown), and at the same time, the lid 61 of the cleaning tank 6 is opened and the nuclear fuel assembly 30 is pulled out into the main body 62 of the cleaning tank 6. suspended inside.

この場合、洗浄槽6の内周フランジ62Fの面a、が核
燃料体30の下部タイブレー)30Dを案内して核燃料
体30の軸心と洗浄槽6の軸心とが自然に一致する。
In this case, the surface a of the inner peripheral flange 62F of the cleaning tank 6 guides the lower tie brake 30D of the nuclear fuel assembly 30, so that the axial center of the nuclear fuel assembly 30 and the axial center of the cleaning tank 6 naturally coincide.

核燃料体30の洗浄槽本体62中への吊り込みが終了し
た後、蓋61が本体62上へ吊り下され、その結果、第
2図に示されるように蓋61は本体62の外周フランジ
62G上に着座し、ランチ62Hによって両者がクラン
プされる。
After the nuclear fuel assembly 30 has been suspended into the cleaning tank main body 62, the lid 61 is suspended onto the main body 62, and as a result, the lid 61 is suspended above the outer peripheral flange 62G of the main body 62, as shown in FIG. , and both are clamped by the launch 62H.

蓋61の吊り下しの時に本体62の外周フランジ62G
の傾斜面すは蓋61のガイドとして働き、蓋61の位置
決めを容易にする。
When the lid 61 is suspended, the outer periphery flange 62G of the main body 62
The inclined surface acts as a guide for the lid 61 and facilitates positioning of the lid 61.

蓋61の閉鎖時に於て、蓋61の内部の可動フランジ6
1Gは柔軟材61Hを介して核燃料体30のチャンネル
ボックス30Bの上端に弾性的に圧接され、核燃料体3
0は洗浄槽6内で動かないように把持される。
When the lid 61 is closed, the movable flange 6 inside the lid 61
1G is elastically pressed against the upper end of the channel box 30B of the nuclear fuel body 30 via the flexible material 61H, and
0 is held in the cleaning tank 6 so as not to move.

次に、洗浄液供給装置7中のポンプ73が起動されると
同時に弁■1〜■4が開かれ、洗浄液が管路P1を通っ
て洗浄槽6中に圧送される。
Next, the pump 73 in the cleaning liquid supply device 7 is started, and at the same time valves 1 to 4 are opened, and the cleaning liquid is pumped into the cleaning tank 6 through the pipe P1.

洗浄液には混合器76によって氷の小塊もしくは低融点
パラフィンの小塊が所定の混合比で混入される。
Small pieces of ice or small pieces of low-melting paraffin are mixed into the cleaning liquid by a mixer 76 at a predetermined mixing ratio.

洗浄槽6中に圧送された洗浄液は第2図に矢印で示すよ
うに洗浄槽6の下方から核燃料体30の燃料棒30Aの
間の流路を上昇し、その間に燃料棒30Aの外周面の付
着物が洗浄液中の固形物質との摩擦によってこすり落さ
れる。
The cleaning liquid pumped into the cleaning tank 6 ascends from the bottom of the cleaning tank 6 through the flow path between the fuel rods 30A of the nuclear fuel assembly 30 as shown by the arrow in FIG. The deposits are rubbed off by friction with solid substances in the cleaning solution.

洗浄液中の固形物質は核燃料体中を流れる間に燃料棒周
面との摩擦及び燃料棒から発生する崩壊熱とによって漸
次融解し、管路P2を通って洗浄液タンク71に還流し
た時には殆んどが融解する。
While flowing through the nuclear fuel assembly, the solid substances in the cleaning liquid gradually melt due to friction with the circumferential surface of the fuel rods and decay heat generated from the fuel rods, and when they return to the cleaning liquid tank 71 through the pipe P2, most of the solid substances are melted. melts.

洗浄液タンク71に還流した洗浄液は汚物分離器72に
於て核燃料体の付着物を除去され、混合器76に於て再
び融解性固形物質が混入される。
The cleaning liquid that has returned to the cleaning liquid tank 71 is sent to a dirt separator 72 to remove deposits from the nuclear fuel assembly, and then to a mixer 76 where meltable solid substances are mixed therein.

洗浄完了後、洗浄液供給装置7が更に数分間運転され、
管路P1゜P2に含まれる洗浄液の浄化が行われる。
After the cleaning is completed, the cleaning liquid supply device 7 is operated for several more minutes.
The cleaning liquid contained in the pipes P1 and P2 is purified.

その後、ポンプ73が停止され、弁■1〜v4が閉じら
れた後、洗浄槽6の蓋61を開いて洗浄槽6内から核燃
料体30を引き出す。
After that, the pump 73 is stopped and the valves (1) to (v4) are closed, and then the lid 61 of the cleaning tank 6 is opened and the nuclear fuel assembly 30 is drawn out from inside the cleaning tank 6.

第1図に示された第一実施例に於ては、洗浄液が常に洗
浄槽6内を一方向に貫流しているが、このように常に一
方向のみに洗浄族を貫流させる方法は洗浄液の流れ方向
を交互に切換える方法に比して洗浄効果が劣るというこ
とが判っている。
In the first embodiment shown in FIG. 1, the cleaning liquid always flows through the cleaning tank 6 in one direction, but this method of always causing the cleaning liquid to flow in only one direction is not suitable for cleaning liquid. It has been found that the cleaning effect is inferior to methods in which the flow direction is alternately switched.

実験によると、核燃料体を第一実施例の方法で洗浄した
場合、最初に洗浄液と接する部分が最もよく洗浄され、
下流側はど洗浄効果が低下することが判明した。
According to experiments, when a nuclear fuel assembly is cleaned using the method of the first embodiment, the parts that come into contact with the cleaning liquid first are cleaned best;
It was found that the cleaning effect on the downstream side was reduced.

そこで、洗浄液の流れの方向を交互に逆転させたところ
、一方向流れの洗浄方法に比してその半分の量の固形物
質を洗浄液に混入するだけで、同じ洗浄効果を得られる
ことが判った。
Therefore, by alternately reversing the flow direction of the cleaning solution, it was found that the same cleaning effect could be obtained by mixing half the amount of solid substances into the cleaning solution compared to a unidirectional flow cleaning method. .

第4図はこの事実を示す線図である。FIG. 4 is a diagram illustrating this fact.

第4図に於て横軸は核燃料体の下端から上端までの長さ
を示し、縦軸は洗浄効果を示す。
In FIG. 4, the horizontal axis shows the length from the bottom end to the top end of the nuclear fuel body, and the vertical axis shows the cleaning effect.

第4図に於て破線で示される曲線■は核燃料体の下端か
ら上端へ洗浄液を貫流させる洗浄方法によって洗浄した
場合の核燃料体全長にわたる洗浄効果を示したもので、
この曲線■から、このような一方向貫流方式による洗浄
では核燃料体の下端に於て最も洗浄効果が大きく、核燃
料体の上端では洗浄効果が急減することが判る。
In Fig. 4, the broken line (■) shows the cleaning effect over the entire length of the nuclear fuel assembly when cleaning is performed by a cleaning method in which the cleaning liquid flows from the lower end to the upper end of the nuclear fuel assembly.
From this curve (2), it can be seen that in cleaning by such a one-way flow-through method, the cleaning effect is greatest at the lower end of the nuclear fuel assembly, and the cleaning effect rapidly decreases at the upper end of the nuclear fuel assembly.

この原因は洗浄液中に混入されている融解性物質が核燃
料体から生ずる崩壊熱のため、核燃料体中を流れる間に
その一部が溶解してしまったり、もしくは減摩してしま
うことにある。
The reason for this is that the meltable substances mixed in the cleaning fluid are partially melted or are reduced in friction while flowing through the nuclear fuel assembly due to the decay heat generated from the nuclear fuel assembly.

第4図に示される曲線■(一点鎖線で表示される曲線)
は曲線■で示される場合に対して洗浄液中の融解性物質
の量を半分にし、かつ、洗浄時間をも半分にした上、核
燃料体の下端から上端へ洗浄液を貫流させた場合の洗浄
効果を示すものである。
Curve shown in Figure 4 ■ (Curve shown as a dashed-dotted line)
shows the cleaning effect when the amount of meltable substances in the cleaning fluid is halved, the cleaning time is also halved, and the cleaning fluid flows from the lower end of the nuclear fuel assembly to the upper end compared to the case shown by curve ■. It shows.

また、二点鎖線で示される曲線■は同じく、曲線■で示
される場合に対して洗浄液中の融解性物質の量と洗浄時
間とを1/2にした上、核燃料体の上端から下端へ洗浄
液を一方向貫流させた場合の洗浄効果を示す。
Similarly, the curve ■ shown by the two-dot chain line has the amount of meltable substances in the cleaning liquid and the cleaning time halved compared to the case shown by the curve ■, and the cleaning liquid flows from the upper end to the lower end of the nuclear fuel body. This shows the cleaning effect when flowing through in one direction.

この曲線■、■から一方向貫流方式によって洗浄する場
合には洗浄族と最初に接触する部分が最もよく洗浄され
ることが判る。
From these curves (1) and (2), it can be seen that when cleaning is performed by the unidirectional flow-through method, the portion that comes into contact with the cleaning group first is cleaned best.

曲線■(実線で示される曲線)は曲線■、■を合成した
合成値を示す曲線であり、この曲線から判るように、洗
浄液の流れ方向を交互に切換えるならば、核燃料体の全
長にわたって洗浄効果のアンバランスを少くすることが
できることを推測できる。
Curve ■ (solid curve) is a curve that shows the composite value of curves ■ and ■.As can be seen from this curve, if the flow direction of the cleaning fluid is alternately switched, the cleaning effect will be increased over the entire length of the nuclear fuel assembly. It can be inferred that the imbalance can be reduced.

第3図はこの結果に基いて構成された第二実施例を示す
ものである。
FIG. 3 shows a second embodiment constructed based on this result.

(第3図に於ては第1図に示された部分と同じ部分は同
じ符号で表示されている。
(In FIG. 3, the same parts as those shown in FIG. 1 are indicated by the same reference numerals.

)第3図に示された実施例に於ては、第1図の洗浄液供
給装置7に於て管路P1.P2間に接続される管路P3
、P4が設けられるとともに管路P3には弁■5が、
また、管路P4には弁■6が、それぞれ設けられている
ことが特徴である。
) In the embodiment shown in FIG. 3, in the cleaning liquid supply device 7 of FIG. 1, the pipe P1. Pipe P3 connected between P2
, P4 are provided, and a valve ■5 is provided in the pipe P3.
Further, a feature is that each of the pipes P4 is provided with a valve (6).

弁■と弁■6とは管路P1から洗浄液を洗浄槽6中に圧
送する時には閉じられ、管路P2から洗浄槽6中に洗浄
液を圧送する時に開かれる。
Valve (2) and valve (2) 6 are closed when the cleaning liquid is forced into the cleaning tank 6 from the pipe P1, and are opened when the cleaning liquid is forced into the cleaning tank 6 from the pipe P2.

従って、第3図に示される横取によれば、洗浄槽6中を
貫流する洗浄液の流れ方向は交互に切換えられ、その結
果、洗浄効果は第1図図示の装置よりも向上し、使用す
る固形物質の量を低減することができる。
Therefore, according to the arrangement shown in FIG. 3, the flow direction of the cleaning liquid flowing through the cleaning tank 6 is alternately switched, so that the cleaning effect is improved compared to the device shown in FIG. The amount of solid material can be reduced.

第5図は、核燃料体を洗浄しないで原子炉の運転を継続
した場合の核燃料体への放射性物質(たとえばコバルト
60)の付着量と、核燃料体を洗浄した場合の核燃料体
への放射能物質の付着量とを示す線図で−あり、実線で
示される曲線Aは洗浄しない場合の放射性物質付着量の
変化を示し、破線で示される曲線Bは一年毎に洗浄した
場合の放射性物質の付着量の変化を示す。
Figure 5 shows the amount of radioactive material (e.g. cobalt-60) deposited on the nuclear fuel assembly when the reactor continues to operate without cleaning the nuclear fuel assembly, and the amount of radioactive material on the nuclear fuel assembly when the nuclear fuel assembly is cleaned. Curve A shown as a solid line shows the change in the amount of radioactive material adhered when not cleaned, and curve B shown as a broken line shows the change in the amount of radioactive material adhered when cleaning is done every year. Shows changes in adhesion amount.

この線図から、核燃料体を一年毎に洗浄することにより
、わずか数年の間に放射性付着物量は大きく違ってくる
ことが判るであろう。
From this diagram, it can be seen that by cleaning the nuclear fuel assembly every year, the amount of radioactive deposits will vary greatly in just a few years.

従って、本発明をたとえば原子力発電所に適用すること
により原子力発電所の安全性を大きく向上することがで
きる。
Therefore, by applying the present invention to, for example, a nuclear power plant, the safety of the nuclear power plant can be greatly improved.

なお、実施例に於ては洗浄槽として密閉容器を用いてい
るが、必ずしも密閉容器でなくともよく、たとえば、燃
料交換プール2の一部を隔絶して使用することもできる
Although a closed container is used as the cleaning tank in the embodiment, it does not necessarily have to be a closed container, and for example, a part of the fuel exchange pool 2 can be used in isolation.

以上のように、本発明によると、洗浄すべき核燃料をプ
ール水中に水没させた状態で洗浄槽に出入し気相との接
触を完全に遮断することができるので、核燃料の取扱い
中の液量防止を遮蔽壁等を特に必要とすることもなく確
実かつ容易に図れるものである。
As described above, according to the present invention, the nuclear fuel to be cleaned can be brought into and out of the cleaning tank while submerged in the pool water, and contact with the gas phase can be completely cut off. Prevention can be achieved reliably and easily without particularly requiring a shielding wall or the like.

また、洗浄槽と圧力容器とをプール水中に共存せしめた
ことにより、炉心から引抜いた核燃料を洗浄槽に即座に
収納して温度融解性固形物質の混入した洗浄液に接触さ
せて洗浄することができ、したがって燃焼中の放射性物
質の崩壊熱に基づく発熱状態を維持させて洗浄作用を行
なわせることにより、固形物質融解用の熱源を特に用意
する必要もなく洗浄液供給部に戻る洗浄液中の固形物質
の融解を行なわせることができる。
Furthermore, by having the cleaning tank and pressure vessel coexist in the pool water, the nuclear fuel extracted from the reactor core can be immediately stored in the cleaning tank and cleaned by contacting it with cleaning liquid mixed with temperature-melting solid substances. Therefore, by maintaining the exothermic state based on the decay heat of the radioactive material during combustion and performing the cleaning action, the solid substances in the cleaning liquid that returns to the cleaning liquid supply section can be removed without the need to prepare a special heat source for melting the solid substances. Melting can be performed.

よって、付着物の分離も容易であり、かつ洗浄槽に洗浄
液が再循環する場合には使用済の固形物質が容易に除去
され、新固形物質による付着物除去作用が能率よく行な
われる等の優れた効果が奏される。
Therefore, it is easy to separate the deposits, and when the cleaning liquid is recirculated to the cleaning tank, the used solid material can be easily removed, and the new solid material can efficiently remove the deposits. effect is produced.

【図面の簡単な説明】[Brief explanation of drawings]

第1図は本発明の第一実施例を示す全体構成図で、第2
図は第1図に示された部分の一部の拡大縦断面図、第3
図は本発明の第二実施例を示す図、第4図は洗浄族の流
れ方向と洗浄効果を示す線区、第5図は洗浄した場合と
洗浄しない場合とにおける核燃料体への放射性付着物の
付着量の比較を示す図である。 符号の説明、1・・・・・・原子炉圧力容器、2・・・
・・・燃料交換用プール、6・・・・・・洗浄槽、7・
・・・・・洗浄液供給部置。
FIG. 1 is an overall configuration diagram showing the first embodiment of the present invention.
The figure is an enlarged vertical sectional view of a part of the part shown in Figure 1,
The figure shows the second embodiment of the present invention, Figure 4 shows the flow direction of the cleaning group and lines showing the cleaning effect, and Figure 5 shows radioactive deposits on the nuclear fuel body with and without cleaning. FIG. 3 is a diagram showing a comparison of adhesion amounts. Explanation of symbols, 1... Reactor pressure vessel, 2...
...Fuel exchange pool, 6...Cleaning tank, 7.
...Cleaning liquid supply unit.

Claims (1)

【特許請求の範囲】 1 原子炉圧力容器が浸漬される燃料交換用プール及び
使用前の核燃料を貯蔵する貯蔵プール等を有した原子炉
施設において使用中の核燃料体を洗浄する洗浄装置にし
て、前記燃料交換用プールもしくは貯蔵プールのプール
水中に水没されるとともに前記プール水から隔絶された
洗浄槽と、前記洗浄槽に接続され前記洗浄槽内に洗浄族
を貫流せしめる洗浄液供給装置とを含み、前記洗浄液供
給装置は、ポンプと、温度融解性固形物質の供給装置と
、汚物分離器と、を有して威る、原子炉施設における使
用中の核燃料体の洗浄装置。 2、特許請求の範囲第1項記載の洗浄装置に於て前記洗
浄液供給装置には前記洗浄槽内における洗浄液の貫流方
向を正逆いずれの向きにも変換しうる切換弁が設けられ
ていることを特徴とする、原子炉施設における使用中の
核燃料体の洗浄装置。 3 特許請求の範囲第1項記載の洗浄装置に於いて洗浄
槽は洗浄液を核燃料体の燃焼棒に接触流通させる流路を
有し、洗浄液供給装置の汚物分離器は環流する洗浄液を
貯溜する洗浄液タンクの下流側に接続され、温度融解性
固型物質の供給装置は形状選別器を介して混合器に接続
され、この混合器が前記汚物分離器の下流側に接続され
て固形物質混入洗浄液を洗浄装置に供給する構成とされ
ていることを特徴とする原子炉施設における使用中の核
燃料体の洗浄装置。
[Scope of Claims] 1. A cleaning device for cleaning a nuclear fuel assembly in use in a nuclear reactor facility having a fuel exchange pool in which a reactor pressure vessel is immersed, a storage pool for storing nuclear fuel before use, etc. A cleaning tank submerged in pool water of the fuel exchange pool or storage pool and isolated from the pool water, and a cleaning liquid supply device connected to the cleaning tank and causing a cleaning group to flow through the cleaning tank, The cleaning liquid supply device is a cleaning device for a nuclear fuel assembly in use in a nuclear reactor facility, and includes a pump, a temperature-melting solid material supply device, and a waste separator. 2. In the cleaning device according to claim 1, the cleaning liquid supply device is provided with a switching valve that can change the flow direction of the cleaning liquid in the cleaning tank to either forward or reverse direction. A cleaning device for nuclear fuel bodies in use in a nuclear reactor facility, characterized by: 3 In the cleaning device according to claim 1, the cleaning tank has a flow path that allows the cleaning fluid to contact and flow through the combustion rods of the nuclear fuel assembly, and the filth separator of the cleaning fluid supply device stores the cleaning fluid that is recycled. A supply device for temperature-melting solid substances is connected to the downstream side of the tank and is connected to a mixer via a shape sorter, and this mixer is connected to the downstream side of the waste separator to remove the solid substance-containing cleaning liquid. A cleaning device for nuclear fuel assemblies in use in a nuclear reactor facility, characterized in that the cleaning device is configured to supply water to the cleaning device.
JP51039207A 1976-04-09 1976-04-09 Cleaning equipment for nuclear fuel bodies in use at nuclear reactor facilities Expired JPS5840719B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP51039207A JPS5840719B2 (en) 1976-04-09 1976-04-09 Cleaning equipment for nuclear fuel bodies in use at nuclear reactor facilities

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP51039207A JPS5840719B2 (en) 1976-04-09 1976-04-09 Cleaning equipment for nuclear fuel bodies in use at nuclear reactor facilities

Publications (2)

Publication Number Publication Date
JPS52122793A JPS52122793A (en) 1977-10-15
JPS5840719B2 true JPS5840719B2 (en) 1983-09-07

Family

ID=12546677

Family Applications (1)

Application Number Title Priority Date Filing Date
JP51039207A Expired JPS5840719B2 (en) 1976-04-09 1976-04-09 Cleaning equipment for nuclear fuel bodies in use at nuclear reactor facilities

Country Status (1)

Country Link
JP (1) JPS5840719B2 (en)

Families Citing this family (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5440683U (en) * 1977-08-26 1979-03-17
JPS5761999A (en) * 1980-10-02 1982-04-14 Nippon Atomic Ind Group Co Method and device for removing clad of fuel assembly
JPS5941800U (en) * 1982-09-10 1984-03-17 株式会社東芝 Nuclear fuel cleaning equipment
SE521742C2 (en) * 1997-05-21 2003-12-02 Westinghouse Atom Ab Device for removing a radioactive coating
US6718002B2 (en) * 1997-05-21 2004-04-06 Westinghouse Atom Ab Method and device for removing radioactive deposits
HUP0201547A3 (en) * 1999-05-21 2003-02-28 Framatome Anp Gmbh Device for purifying and/or decontaminating fuel elements

Also Published As

Publication number Publication date
JPS52122793A (en) 1977-10-15

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